|
E 1.99:ornl/tm-7634
|
Validation tests of the venture finite-difference diffusion theory neutronics code. [LMFBR] |
1 |
|
E 1.99:ornl/tm-7637
|
Dosimetry report for the Sandia irradiator for dried sewage solids |
1 |
|
E 1.99:ornl/tm-7645
|
Theoretical evaluation of a mechanism of precipitate-enhanced cavity swelling during irradiation |
1 |
|
E 1.99:ornl/tm-7646
|
Chemical Characteristics of Two Forested Ultisols and Two Forested Inceptisols Relevant to Anion Production and Mobility |
1 |
|
E 1.99:ornl/tm-7647
|
Calculated differential. pi. /sup +/ production spectra at large angles from 28 GeV protons on a thick iridium target and comparisons with experimental data |
1 |
|
E 1.99:ornl/tm-7650
|
Testing of bellows for engineering systems. Part II |
1 |
|
E 1.99:ornl/tm-7651
|
Production of spherical UO/sub 2/-UC/sub 2/ for nuclear fuel applications using thermochemical principles |
1 |
|
E 1.99:ornl/tm-7652
|
Uranium recovery from low-level aqueous sources. [76 references] |
1 |
|
E 1.99:ornl/tm-7653
|
Volume reduction of solid waste by biological conversion of cellulosics |
1 |
|
E 1.99:ornl/tm-7656
|
Beam specie analyzer for intense neutral beams |
1 |
|
E 1.99:ornl/tm-7658
|
Neutral-beam deposition in large, finite-beta noncircular tokamak plasmas |
1 |
|
E 1.99:ornl/tm-7665
|
Using GIFTS on the Cray-1 for the large coil test facility test stand design analysis. |
1 |
|
E 1.99:ornl/tm-7670
|
Experimental procedure for examining the kinetics of tritium gas conversion to tritiated water |
1 |
|
E 1.99:ornl/tm-7671
|
Disintegration and size reduction of slags and metals after melt refining of contaminated metallic wastes |
1 |
|
E 1.99:ornl/tm-7673
|
Progress report for the Office of Safeguards and Security for FY 1980 |
1 |
|
E 1.99:ornl/tm-7674
|
Performance of HTGR biso- and triso-coated fertile particles irradiated in capsule HT-34 |
1 |
|
E 1.99:ornl/tm-7675
|
US-Japan Workshop on atomic-collision data for fusion |
1 |
|
E 1.99:ornl/tm-7678
|
Equilibrium evolution on the resistive time scale in a tokamak reactor |
1 |
|
E 1.99:ornl/tm-7681
|
Silica scaling in simulated geothermal brines |
1 |
|
E 1.99:ornl/tm-7684
|
Evaluation of gravimetric and volumetric dispensers of particles of nuclear material. [Accurate dispensing of fissile and fertile fuel into fuel rods] |
1 |
